ML20079G246
| ML20079G246 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 01/05/1984 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19289B673 | List: |
| References | |
| NUDOCS 8401190542 | |
| Download: ML20079G246 (9) | |
Text
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SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET N0. 50-395 VIRGIL C. SUMMER NUCLEAR STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 20 License No. NPF-12 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Virgil C. Summer Nuclear Station, Unit No.1 (the facility) Facility Operating License No. NPF-12 filed by the South Carolina Electric & Gas Company acting for itself and South Carolina Public Service Authority (the licensees), dated July 22, 1983, complies with the standards and requirements of the Atonic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission'*, regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this license amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page ci;3nges to the Technical Specifications as indicated in the attachments to this license amendment and paragraph 2.C(2) of Facility Operating License No. NPF-12 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 2Q are hereby incorporated into this license.
South Carolina Electric & Gas Cnmpany shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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3.
This license amendment is effective as of ~its date of issuance.
FOR THE NUCLEAR REGULATORY COM11SSION i
Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Enclosure:
Technical Specification Changes Date of Issuance: January 5, 1984 4
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ATTACHMENT TO LICENSE AMENDMENT NO 20 FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain_ vertical lines indicating the area of change. The corresponding over-leaf pages are also provided to maintain document completeness.
, Amended Overleaf Page Page 3/4 3-68 3/4 3-67 3/4 3-70 3/4 3-69 3/4 3-71 3/4 3-72 1
L
IN$TRUMENTATION RADIOACTkVELIQUID*EFFLUENTMONITCRINGINSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive liquid effluent acnitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.
The alarm /
trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
APPLICABILITY:
At all times.
ACTION:
a.
With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid' effluents monitored by the affected channel or declare the channel inoperable.
b.
With less than t.he minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.
Additionally if this condition prevails for more than 30 days, in the next semiannual effluent report, explain why this condition was not corrected in a timely manner.
c.
The provisions of Specifications 6.9.1.12.b, 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS -4.3.3.8.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-8.
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i SUMMER - UNIT 1 3/4 3-67 1
.a...
E TABLE 3.3-12 E9 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION C*
MINIMUM
-d CHANNELS INSTRUMENT OPERABLE ACTION 1.
GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.
Liquid Radwaste Effluent Line - RM-L5 or RM L9 1
31 b.
Nuclear (Processed Steam Gener5 tor) Blowdown Effluent 1
31 Line RM-L7 or RM-L9 c.
Steam Generator Blowdown Effluent Line 1.
Unprocessed during Power Operation - RM-L10 or RM-L3 1
32 t'
2.
Unprosessed during Startup - RM-L3 1
32 s
i' d.
Turbine Building Sump Effluent Line - RM-L8 1
33 e.
Condensate Demineralizer Backwash Effluent Line RM-L11 1
36 2.
FLOW RATE MEASUREMENT DEVICES
- a.
Liquid Radwaste Effluent Line - Tanks 1 and 2 1/ tank 34 b.
Penstocks Minimum Flow Interlock **
1 34 c.
Nuclear Blowdown Effluent Line 1
34 d.
Steam Generator (Unprocessed) Blowdown Effluent Line 1
34 3.
TANK LEVEL INDICATING DEVICES
!f a.
Condensate Storage Tank 1
35 E
a E
- Flow rate for the monitor RM-L9 is determined by adding flow rates for monitors RM-L5 and RM-L7.
- Minimum dilution flow is assured by an interlock terminating liquid waste releases if minimum
=
dilution flow is not available.
E$
INSTRUMENTATION TABLE 3.3-12 (Continued)
TABLE NOTATION ACTION 31 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue for up to 14 days provided that prior to initiating a release:
a.
At least two independent samples are analyzed in accordance with Specification 4.11.1.1.3, snd b.
At least two technically qualified members of the Facility Staff. independently c2rify the release rate calculations and discharge line valving; Otherwise, suspend releass of radioactive effluents via this pathway.
ACTION 32 -
With the number of channels OFERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continua for up to 30 days provided grab samples are analyzed for gross radioactivity (beta and gamma) at a limit of detection of at least 10 7 microcuries/ gram:
a.
At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcuries/ gram DOSE EQUIVALENT I-131.
b.
At lea'st once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 micro-curies / gram DOSE EQUIVALENT I-131.
ACTICN 33 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, grab samples are collected and analyzed for gross radioactivity (beta and gamma) at a limit of detection of at least 10 7 microcuries/ gram.
ACTION 34 -
With the number of channels OPERABLE less than required by the Minimum ^?hanneis OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
Pump curves may be used to estimate flow.
SUMMER - UNIT 1 3/4 3-69
INSTRUMENTATION TABLE 3.3-12 (Continued)
TABLE NOTATION ACTION 35 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue for up to 30 days provided the tank liquid level is estimated during all liquid additions to the tank to prevent overflow.
ACTION 36 With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, effluent releases may continue for up to 30 days provided that samples are analyzed in accordance with specification 4.11.1.1.1 and 4.11.1.5.
SUMMER - UNIT 1 3/4 3-70 Amendment No. 20
TABLE 4.3-8
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ii E
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS C5 ANALOG CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST 1.
GROSS BETA OR GAMMA RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Effluent Line - RM-L5, RM-L9 D
P R(3)
Q(1)
- b. Nuclear Blowdown Effluent Line - RM-L7 D
P R(3)
Q(1)
- c. Steam Generator Blowdown Effluent Line -
D M
R(3)
Q(1) j;'
RM-L3, RM-LIG Y
- d. Turbine Building Sump d
Effluent Line - RM-L8 D
M R(3)
Q(1)
- e. Condensate Demineralizer Ba'ckwash Line RM-L11 D M
R(3)
Q(5) 2.
FLOW RATE MEASUREMENT DEVICES
- a. Liquid Radwaste Effluent Line D(4)
N.A.
R Q
- b. Penstocks Minimum Flow Interlock D(4)
N.A.
R Q
- c. Nuclear Blowdown Effluent Line D(4)
N.A.
R Q
- d. Steam Generator Blowdown D(4)
N.A.
R Q
[
Effluent Line C
3.
TANK LEVEL INDICATING DEVICES oo
- a. Condensate Storage Tanks D
N.A.
R Q
INSTRUMENTATION TABLE 4.3-8 (Continued)
TABLE NOTATION (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic
' isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Loss of Power (alarm only).
3.
Instrument indicates a downscale failure (alarm only).
4.
Instrument controls not set in operate mode.
(2) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
2.
Loss of Power.
3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in operate mode.
(3) Tne initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance a' tivities with NBS.
These standcrds shall c
permit calibrating the system over its intended range of energy and measurament range.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
(5) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that auto-matic isolation of this pathway and local panel alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Loss of Power (alarm only).
3.
Instrument indicates a downscale failure (alarm only).
4.
Instrument controls not set in operate mode.
SUMMER - UNIT 1 3/4 3-72 Amendment No. 20